Session: CS-19-04 European Project FRACTESUS for mini-CT Master Curve - 2
Paper Number: 105918
105918 - Numerical Prediction of Fracture Toughness of a Reactor Pressure Vessel Steel Based on Experiments Using Small Specimens
Due to limited availability of irradiated material and safety concerns when testing large irradiated specimens, a major effort is being made in nuclear materials research to establish small specimen testing techniques for determining the fracture resistance of reactor pressure vessel (RPV) steels. The ASTM E1921 standard is used extensively to estimate fracture toughness of ferritic steels in the ductile-to-brittle transition region. As a consequence of the inherent low constraint of small specimens, many test results exceed the fracture toughness limit specified in the standard, resulting in wasted material. To avoid this problem, finite element analysis using the cohesive zone model is applied to predict the fracture toughness of standard-sized specimens based on small specimen test results. Those tests were carried out within the framework of the FRACTESUS project using compact tension specimens with a thickness of 4 mm. The parameters of the cohesive zone model are calibrated by means of a hybrid experimental-numerical approach. After identification of the parameters on small specimens, the simulation of a standard-sized geometry is performed and the resulting fracture toughness values are compared to the small specimen data.
This project has received funding from the Euratom research and training programme 2020-2024 under grant agreement No 900014.
Presenting Author: Timo Metzler Karlsruhe Institute of Technology
Presenting Author Biography: - Bachelor's degree in Mechanical Engineering from Karlsruhe Institute of Technology
- Master's degree in Mechanical Engineering from Karlsruhe Institute of Technology
- Third year PhD student at Karlsruhe Institute of Technology, specializing in fracture mechanics testing and simulation of nuclear materials
Authors:
Timo Metzler Karlsruhe Institute of TechnologyErmile Gaganidze Karlsruhe Institute of Technology
Jarir Aktaa Karlsruhe Institute of Technology
Numerical Prediction of Fracture Toughness of a Reactor Pressure Vessel Steel Based on Experiments Using Small Specimens
Paper Type
Technical Paper Publication